KR101669131B1 - A radioactive liquid waste treatment system - Google Patents
A radioactive liquid waste treatment system Download PDFInfo
- Publication number
- KR101669131B1 KR101669131B1 KR1020160008712A KR20160008712A KR101669131B1 KR 101669131 B1 KR101669131 B1 KR 101669131B1 KR 1020160008712 A KR1020160008712 A KR 1020160008712A KR 20160008712 A KR20160008712 A KR 20160008712A KR 101669131 B1 KR101669131 B1 KR 101669131B1
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- KR
- South Korea
- Prior art keywords
- waste liquid
- evaporation
- liquid waste
- evaporation vessel
- tank
- Prior art date
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F25—REFRIGERATION OR COOLING; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS; MANUFACTURE OR STORAGE OF ICE; LIQUEFACTION SOLIDIFICATION OF GASES
- F25B—REFRIGERATION MACHINES, PLANTS OR SYSTEMS; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS
- F25B39/00—Evaporators; Condensers
- F25B39/04—Condensers
-
- F25B41/046—
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01F—MEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
- G01F23/00—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm
- G01F23/22—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water
- G01F23/28—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water by measuring the variations of parameters of electromagnetic or acoustic waves applied directly to the liquid or fluent solid material
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F25—REFRIGERATION OR COOLING; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS; MANUFACTURE OR STORAGE OF ICE; LIQUEFACTION SOLIDIFICATION OF GASES
- F25B—REFRIGERATION MACHINES, PLANTS OR SYSTEMS; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS
- F25B2339/00—Details of evaporators; Details of condensers
- F25B2339/04—Details of condensers
- F25B2339/044—Condensers with an integrated receiver
- F25B2339/0441—Condensers with an integrated receiver containing a drier or a filter
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Thermal Sciences (AREA)
- General Engineering & Computer Science (AREA)
- Electromagnetism (AREA)
- Fluid Mechanics (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
Abstract
Description
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a radioactive waste liquid evaporation and drying system, and more particularly, to a radioactive liquid waste evaporation and drying system in which radioactive liquid waste can be evaporated while circulating a vapor container and a heater outside the vapor container.
Nuclear fuel refers to a substance that is charged into a nuclear reactor to produce a chain of fissionable energy to obtain available energy. Radioactive waste is a substance that necessarily occurs in the process of using nuclear fuel. Radioactive waste can be divided into solids, liquids and gases.
Two radioactive liquid wastes contain several percent of non radioactive material (dust, soil, sludge, synthetic detergent, oil, etc.) and radioactive materials (Ag, Fe, B, Si, Mg, Ca, Al, Ti, S, Na, K, etc.) are generated in laboratory system, laundry wastewater, system decontamination water, floor drainage.
Such radioactive liquid wastes will inevitably occur due to the use of nuclear power generation, nuclear fuel cycle facilities and radioactive isotopes, and must be safely treated and managed so that they will not be harmed for a long period of time.
At this time, the treatment for the radioactive liquid waste is evaporated and concentrated for volume reduction.
The evaporation concentrating treatment system for such radioactive liquid wastes is not only a large facility but also a small concentration waste liquid evaporator drier which is manufactured by a liver transplant using a band heater is also used.
At this time, the conventional small concentrated liquid waste liquid evaporator has the following problems.
First, the band heater type small evaporation dryer is advantageous in that it can be constructed in a compact manner because evaporation and drying are performed together in a single vessel. However, since concentrated waste liquid in the vessel is not circulated and is heated in a static state, It is possible to cause carryover or Dolby phenomenon.
Accordingly, there has been a problem that the flow rate of the evaporation treatment is decreased as compared with the designed capacity as the heat output of the band heater is lowered to prevent the carryover and the Dolby phenomenon.
In other words, there has been a problem that the efficiency of equipment operation is deteriorated due to the above-described problem.
Secondly, the concentrated waste liquid in the container is not circulated and is heated in a static state. Therefore, due to the band heater installed in the container in the portion where the level of the waste liquid does not reach, fine deformation may occur in the container during decompression operation or long- , Which leads to a problem that the mechanical life of the container is shortened.
Third, since the method for controlling the level of the waste water in the container is simple on / off method, the evaporation process is stable since the waste liquid is intermittently supplied to the inside of the container according to the level of the waste water, There is a problem that the evaporation flow rate temporarily decreases.
Fourth, since the water level meter for measuring the level of the waste water in the container is provided in the float type, there is a problem that the water level is interfered with the water level meter when using for a long period of time.
SUMMARY OF THE INVENTION The present invention has been conceived to solve the problems described above, and it is an object of the present invention to provide an apparatus and a method for circulating a radioactive waste solution through a circulation pump and a heater, And to provide a system for evaporating and drying a radioactive liquid waste so that operation can be performed stably without occurrence of a phenomenon.
According to an aspect of the present invention, there is provided a waste liquid supply system including a waste liquid supply tank in which a radioactive waste liquid is stored, an evaporation container in which a radioactive waste liquid is evaporated and dried, And a waste liquid circulation channel provided between the evaporation vessel and the heater and circulating the radioactive waste liquid in the evaporation vessel to the heater and the evaporation vessel, Wherein the waste liquid supply tank and the evaporation container are installed in a storage tank and a collection groove is formed in the storage tank for collecting the radioactive waste solution that has leaked from the waste liquid supply tank and the evaporation container rotor and is disposed between the collection groove and the waste liquid supply tank; A water level meter for measuring the water level of the collection groove; a water level meter for measuring a water level, And a waste liquid recovery pump for recovering the radioactive waste liquid in the collection groove through the waste liquid recovery tank.
At this time, a pressure regulating passage is provided between the waste liquid supply passage and the waste liquid supply tank, and a valve for controlling the amount of opening and closing of the pressure regulating passage is provided in the pressure regulating passage.
Preferably, a heat exchanger for exchanging the temperature of the radioactive waste liquid supplied from the waste liquid feed water tank is further provided on the waste liquid feed passage.
At this time, it is preferable that a steam energy recovery flow path is provided between the heat exchanger and the evaporation container, and the heat exchange action of the heat exchanger is performed using high temperature steam supplied through the steam energy recovery flow path.
A condenser provided at one side of the evaporation vessel, a steam supply channel provided between the condenser and the heat exchanger, the steam supply channel providing a channel through which heat-exchanged steam is introduced into the condenser, a discharge channel through which the condensed water generated from the condenser is discharged, .
The condenser water circulation passage includes a condensate water tank connected to the discharge passage, a condensate water circulation pump connecting the condensed water tank and the discharge passage and circulating the condensate water in the condensed water tank, an aspirator provided in the discharge passage and the condensate circulation passage, : ≪ / RTI >
It is preferable that the evaporation vessel is provided with a radar type water level meter for measuring the level of the radioactive waste liquid.
delete
It is preferable that a band heater is installed below the outer circumferential surface of the evaporation vessel.
The radioactive liquid waste evaporation and drying system according to the present invention has the following effects.
First, the waste liquid in the evaporation vessel is circulated through the heater and the evaporation vessel provided outside the evaporation vessel, and the evaporation operation is performed through the band heater installed at the lower side of the outer side of the evaporation vessel, It is possible to prevent a Dolby phenomenon or a carryover phenomenon that may occur.
Thereby, the system operation can be stably performed.
Secondly, since the waste liquid is heated while being in direct contact with the heater, the efficiency of heat transfer is improved and the efficiency of the evaporation of the waste liquid can be enhanced.
That is, the heating by the direct method is performed instead of the heating by the indirect method, so that the efficiency of heat transfer to the waste liquid is increased, the evaporation processing time is shortened, and the workability is improved.
Third, since the heater installed outside the evaporation vessel can be provided only under the outer circumferential surface of the evaporation vessel, the evaporation vessel can be deformed even during decompression operation or long-term operation to prevent the mechanical lifetime from being shortened There is an effect that can be.
Fourth, since the flow rate of the waste liquid supplied to the evaporation vessel and the flow rate of the condensed water discharged through the condenser can correspond to each other through the pressure control of the pressure regulating passage, the steam energy is recovered by the heat exchanger, There is an effect that the preheating of the waste liquid can be stably performed.
Further, since the flow rate of the waste liquid container in the evaporation vessel can be maintained constant, the temperature of the waste liquid in the evaporation vessel is not changed due to the additional supply of waste liquid, so that the evaporation operation can be stably performed.
Fifth, the water level meter for measuring the level of the wastewater in the evaporation vessel is provided in a radar manner, so that the water level measurement can be performed without direct contact with the waste liquid.
Accordingly, it is possible to prevent errors in the water level measurement due to the formation of foreign substances and scales in the water level meter, and it is easy to maintain the water level meter.
Sixth, by using the condensate circulation generated from the condenser, depressurization operation is performed inside the evaporation container, noise can be prevented, and energy efficiency can be improved.
Seventh, the waste liquid supply tank and the evaporation container are installed in the storage tank, and the storage tank is provided with a waste liquid recovery pump for recovering the waste liquid leaked from the waste liquid supply tank and the evaporation container to the waste liquid supply water tank, thereby preventing the radioactive waste liquid from leaking to the outside There is an effect that can be done.
BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a block diagram of a system for vaporizing and drying a radioactive liquid waste according to a preferred embodiment of the present invention; FIG.
It is to be understood that the words or words used in the present specification and claims are not to be construed in a conventional or dictionary sense and that the inventor can properly define the concept of a term in order to describe its invention in the best possible way And should be construed in light of the meanings and concepts consistent with the technical idea of the present invention.
Hereinafter, a system for evaporating and drying a radioactive liquid waste according to a preferred embodiment of the present invention will be described with reference to FIG.
The radioactive liquid waste evaporation and drying system has a technical feature that the radioactive waste liquid can be evaporated in the evaporation vessel while circulating through the heater and the evaporation vessel outside the evaporation vessel.
Accordingly, it is possible to prevent the dolby phenomenon and the carry over phenomenon in the evaporation vessel, so that the waste liquid evaporation operation of the system can be stably performed.
The waste liquid evaporation and drying system for this purpose includes a
The
At this time, the
At one side of the
The collecting
The bottom surface of the
At this time, the
A waste
The waste liquid
Next, the
In addition, a plurality of
In addition, a
A
This is to increase the accuracy of the water level measurement by minimizing the occurrence of malfunctions in the
On the other hand, the
The
That is, the
The
The driving
The
It is preferable that the
That is, since the
It is preferable that a
This is intended to be used as an important factor for determining the end point of the evaporation operation and the drying operation by measuring the rotational load of the
The waste
The waste
At this time, the waste
The
At this time, the thermal energy for heat exchange of the waste liquid collects the high-temperature steam generated when evaporating the waste liquid in the
For this, a vapor energy recovery flow path 440 is provided between the upper part of the
A waste
On the other hand, the waste
The
The
At this time, a
With this configuration, the pressure of the waste
Next, the heater serves to heat and evaporate the waste liquid supplied into the evaporation vessel, and is installed at one side of the evaporation vessel.
At this time, the
This is to increase the heating efficiency of the waste liquid, and to facilitate maintenance such as inspection and replacement of the
Next, the waste liquid circulating flow path serves to circulate the waste liquid in the vaporizing container between the heater and the vaporizing container.
The waste liquid is directly contacted to the
The waste
Next, the
To this end, a
The
At this time, the
Further, it is preferable that a
Next, the
The
Next, the
At this time, an
In addition, a
At this time, a
On the other hand, a cleansing
The cleaning
Hereinafter, the operation of the evaporation and drying system of the radioactive liquid waste constructed as described above will be described.
The waste liquid supply pipe S is opened to store the waste liquid in the waste
Next, the waste
At this time, the flow rate of the waste liquid supplied through the waste
At this time, the waste liquid supply flow rate is set to coincide with the condensate water flow rate, and the current level of the waste liquid in the
Accordingly, during the evaporation operation, the waste liquid is supplied at a substantially constant flow rate, so that the level of the waste liquid in the
The waste liquid conveyed along the waste
At this time, the waste liquid flows into the
The thermal energy of the
Hereinafter, the operation of evaporation and drying operation in the
The waste liquid which has been heat-exchanged through the
Thereafter, the heated waste liquid flows back into the
On the other hand, as the
At this time, the dried solids are discharged through the
Meanwhile, in the process of evaporation operation in the
As the
At this time, the solid matter adsorbed on the inner surface of the
Since the rotational force load of the
Next, the continuous evaporation operation is performed as described above, and the steam heat-exchanged in the
Thereafter, the steam is converted into condensed water through the
In this case, the amount of discharged condensed water is measured through the
Also, the discharged condensed water is measured by the
Next, the condensed water discharged through the
Meanwhile, depressurization operation of the
The condensing
At this time, the condenser
The decompression operation using the
At this time, when the condensate discharge is required during the depressurization operation of the
This completes the treatment of the radioactive liquid waste by evaporation and drying.
Meanwhile, the waste liquid may leak from the waste
Thereafter, when the waste liquid flows into the collecting
Meanwhile, the above-described system for evaporating and drying the waste liquid waste may be fixedly operated at a specific place, or may be installed movably in a container structure.
That is, the radioactive liquid waste evaporation and drying system may be provided in a movable type, which is installed in a container structure of a type that can be loaded on a vehicle, and may be moved to a required place and operated.
As described above, the system for the evaporation and drying of the radioactive liquid waste according to the present invention is characterized in that the radioactive waste liquid is treated through evaporation and drying so that the waste liquid circulates through the external heater to evaporate, There is a technical feature that the waste liquid can be evaporated after the waste liquid is preheated by using steam.
Accordingly, the evaporation operation can be performed stably and the energy consumption for the evaporation operation can be reduced.
While the present invention has been particularly shown and described with reference to exemplary embodiments thereof, it is evident that many alternatives, modifications and variations will be apparent to those skilled in the art.
100: storage tank 110: bottom surface
111: Water collecting groove 112,330: Water level meter
120: step 130: waste liquid collection pump
140: Waste liquid recovery flow channel 200: Waste liquid supply water tank
300: evaporation vessel 310: band heater
320: discharging part 340: solids peeling device
341: driving
342: rotating shaft 343: peeling blade
400: waste liquid supply flow path 410,461,940: valve
420,721: Flow meter 430: Heat exchanger
440: Steam energy recovery channel 450: Waste liquid supply pump
460: Pressure regulating passage 500: Heater
600: waste liquid circulation flow path 610: waste liquid circulation pump
700: condenser 710: steam supply line
720: Exhaust flow path 722: Condensate conduction meter
800: Condensate tank 900: Condensate circulation flow path
910: Aspirator 920: Condensate circulation pump
930: Condensate discharge pipe 950: Cleansing water supply channel
S: Waste water supply and demand organ
Claims (9)
An evaporation vessel in which the radioactive waste liquid is evaporated and dried;
A waste liquid supply passage provided between the waste liquid supply tank and the evaporation container and including a waste liquid supply pump;
A heater installed at one side of the evaporation vessel;
And a waste liquid circulation channel provided between the evaporation vessel and the heater and circulating the radioactive waste liquid in the evaporation vessel to the heater and the evaporation vessel,
The waste liquid supply tank and the evaporation vessel are installed in a storage tank,
The storage tank is provided with a collection groove for collecting the waste liquid supply water tank and the radioactive waste liquid leaked from the evaporation container rotor,
A waste liquid recovery flow path provided between the collection groove and the waste liquid supply tank;
A water level meter for measuring the water level of the collection groove;
And a waste liquid recovery pump for recovering the radioactive waste liquid in the collection groove through the waste liquid recovery flow path when the water level exceeds a certain level through the measurement of the water level meter.
A pressure regulating passage is provided between the waste liquid supply passage and the waste liquid supply water tank, and a valve for controlling the amount of opening and closing of the pressure regulating passage is provided in the pressure regulating passage.
On the waste liquid feed path,
Further comprising a heat exchanger for heat-exchanging the temperature of the radioactive waste liquid supplied from the waste liquid supply water tank.
Wherein a steam energy recovery passage is provided between the heat exchanger and the evaporation vessel and the heat exchange action of the heat exchanger is performed using high temperature steam supplied through the steam energy recovery passage.
A condenser installed at one side of the evaporation vessel;
A steam supply passage provided between the condenser and the heat exchanger and providing a conduit through which the heat-exchanged steam is sent to the condenser;
And a discharge flow path through which the condensed water generated from the condenser is discharged.
A condensate tank connected to the discharge passage;
A condensate circulation pump for connecting the condensed water tank to the discharge passage and for circulating the condensed water in the condensed water tank;
And an aspirator provided in the discharge flow path and the condensate circulation flow path.
Wherein the evaporation vessel is provided with a radar type water level meter for measuring the level of the radioactive waste liquid.
And a band heater is installed below the outer circumferential surface of the evaporation vessel.
Priority Applications (1)
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KR1020160008712A KR101669131B1 (en) | 2016-01-25 | 2016-01-25 | A radioactive liquid waste treatment system |
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KR1020160008712A KR101669131B1 (en) | 2016-01-25 | 2016-01-25 | A radioactive liquid waste treatment system |
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Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112722624A (en) * | 2020-12-07 | 2021-04-30 | 广东电网有限责任公司佛山供电局 | Laboratory waste liquid automatic transfer device |
CN113963833A (en) * | 2021-11-30 | 2022-01-21 | 中国原子能科学研究院 | Heat pump evaporation treatment system and method for radioactive waste liquid treatment |
KR102563540B1 (en) | 2022-02-16 | 2023-08-04 | (주)나일프렌트 | Drying system for waste material |
Citations (4)
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JPH10206594A (en) * | 1997-01-21 | 1998-08-07 | Hitachi Ltd | Method and device for disposing of radioactive waste |
KR100675769B1 (en) | 2003-02-27 | 2007-01-29 | (주)이엔이 | Process of Radioactive Liquid Waste |
JP2013134055A (en) * | 2011-12-22 | 2013-07-08 | Osamu Yamada | Method for separating cesium from cesium adsorbed solid substance and system for separating cesium by utilizing the method |
KR101585455B1 (en) * | 2014-10-31 | 2016-01-15 | 한국수력원자력(주) | Treatment equipment of radioactive liquid wastes |
-
2016
- 2016-01-25 KR KR1020160008712A patent/KR101669131B1/en active IP Right Grant
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH10206594A (en) * | 1997-01-21 | 1998-08-07 | Hitachi Ltd | Method and device for disposing of radioactive waste |
KR100675769B1 (en) | 2003-02-27 | 2007-01-29 | (주)이엔이 | Process of Radioactive Liquid Waste |
JP2013134055A (en) * | 2011-12-22 | 2013-07-08 | Osamu Yamada | Method for separating cesium from cesium adsorbed solid substance and system for separating cesium by utilizing the method |
KR101585455B1 (en) * | 2014-10-31 | 2016-01-15 | 한국수력원자력(주) | Treatment equipment of radioactive liquid wastes |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112722624A (en) * | 2020-12-07 | 2021-04-30 | 广东电网有限责任公司佛山供电局 | Laboratory waste liquid automatic transfer device |
CN113963833A (en) * | 2021-11-30 | 2022-01-21 | 中国原子能科学研究院 | Heat pump evaporation treatment system and method for radioactive waste liquid treatment |
CN113963833B (en) * | 2021-11-30 | 2023-10-24 | 中国原子能科学研究院 | Heat pump evaporation treatment system and method for radioactive waste liquid treatment |
KR102563540B1 (en) | 2022-02-16 | 2023-08-04 | (주)나일프렌트 | Drying system for waste material |
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